ARIES: Fusion Power Core and Power Cycle Engineering

Transcription

1 ARIES: Fusion Power Core and Power Cycle Engineering The ARIES Team Presented by A. René Raffray ARIES Peer Review Meeting University of California, San Diego ARIES: Fusion Power Core and Power Cycle Engineering/ARR 1

2 Presentation Outline Power Core and Power Cycle Engineering: Power Cycle Blanket Divertor Material Approach Relies on: Detailed Analysis Using up-to-date analysis tools Developing tools for specific analytical needs Application of creative solutions to extend design window Building Block build on previous ARIES design experience in bettering the end product Community Interaction utilize national and international community input in evolving material properties and component parameters develop clear goals for R&D program showing benefits ARIES: Fusion Power Core and Power Cycle Engineering/ARR 2

3 Power Cycle: Quest for High Efficiency Conventional Steam Cycle: Steel/Water h = 35% ARIES-RS Li/V Supercritical Rankine (water): h = 45% ARIES-ST FS/He/Pb-17Li Brayton (Low Temp. He): h > 45% ARIES-AT (SiC/SiC)/Pb-17Li Brayton (High Temp. He): h = 59% High efficiency translates in lower COE and lower heat load Brayton cycle is best near-term possibility of power conversion with high efficiency T 9 8 9' 6 7' 4 5' 10 Intercooler 1 Intercooler ' S 9 10 Recuperator PbLi Divertor + Blanket Coolant Intermediate HX Maximize potential gain from high-temperature operation with SiC/SiC Compatible with liquid metal blanket through use of IHX Compressor 1 Compressor 3 Compressor Heat Rejection HX Turbine Wnet ARIES: Fusion Power Core and Power Cycle Engineering/ARR 3

4 Brayton Cycle Based on Near-Term Technology and Advanced Recuperator Design Yields High Efficiency Advanced Brayton cycle developed with expert input from GA and FZK, Karlsruhe FZK/UCSD ISFNT-4 paper, 1997 GA/UCSD ANS TOFE-14 paper, 2000 Min. He Temp. in cycle (heat sink) = 35 C 3-stage compression with 2 inter-coolers Turbine efficiency = 0.93 Compressor efficiency = 0.88 Recuperator effectiveness = 0.96 Cycle He fractional DP = 0.03 Total compression ratio set to optimize system (= 2-3) ARIES: Fusion Power Core and Power Cycle Engineering/ARR 4

5 High Efficiency Requires High Temperature Operation Conventionally, maximum coolant temperature is limited by structural material maximum temperature limit Innovative design solutions in ARIES-ST and ARIES-AT allow the blanket coolant exit temperature to be higher than the structure temperature ARIES: Fusion Power Core and Power Cycle Engineering/ARR 5

6 ARIES-ST Utilizes a Dual Coolant Approach to Uncouple Structure Temperature from Main Coolant Temperature ARIES-ST: Ferritic steel+pb-17li+he Flow lower temperature He ( C) to cool structure and higher temperature Pb-17Li ( C) for flow through blanket He-cooled Ferritic Steel ARIES-ST breeding zone cell SiC Pb 83 Li ARIES: Fusion Power Core and Power Cycle Engineering/ARR 6

7 ARIES-AT Utilizes a 2-Pass Coolant Approach to Uncouple Structure Temperature from Outlet Coolant Temperature ARIES-AT: 2-pass Pb-17Li flow, first pass to cool SiC/SiC box and second pass to superheat Pb-17Li Maintain blanket SiC/SiC temperature (~1000 C) < Pb-17Li outlet temperature (~1100 C) ARIES: Fusion Power Core and Power Cycle Engineering/ARR 7

8 Detailed Modeling and Analysis Required to Demonstrate Blanket Performance Multi-dimensional neutronics analysis Latest data and code Tritium breeding requirement influences blanket material and configuration choices Blanket volumetric heat generation profiles used for thermal-hydraulic analyses ARIES: Fusion Power Core and Power Cycle Engineering/ARR 8

9 Accommodation of Material Temperature Limits Verified by Detailed Modeling Moving Coordinate Analysis to Obtain Pb-17Li Temperature Distribution in ARIES-AT First Wall Channel and Inner Channel under MHD-Laminarization Effect First Wall Channel v back q'' plasma Pb-17Li q'' back Inner Channel Poloidal q''' LiPb Radial v FW ARIES-AT Outboard Blanket Segment SiC/SiC First Wall Out SiC/SiC Inner Wall ARIES: Fusion Power Core and Power Cycle Engineering/ARR 9

10 Temperature Distribution in ARIES-AT Blanket Based on Moving Coordinate Analysis Pb-17Li Outlet Temp. = 1100 C Poloidal distance (m) Max. SiC/PbLi Interf. Temp. = 994 C Radial distance (m) Pb-17Li Inlet Temp. = 764 C SiC/SiC Pb-17Li Use plasma heat flux poloidal profile Use volumetric heat generation poloidal and radial profiles Iterate for consistent boundary conditions for heat flux between Pb-17Li inner channel zone and first wall zone Calibration with ANSYS 2-D results FW Max. CVD and SiC/SiC Temp. = 1009 C and 996 C Neutron Wall Load (MW/m2) Average Neutron Wall Load = 3.19 MW/m2 OUTBOARD DIV. INBOARD Poloidal Distance from Lower Outboard (m) ARIES: Fusion Power Core and Power Cycle Engineering/ARR 10

11 Detailed Stress Analysis Using Latest Tool for Maintaining Conservative Design Margins Example of 2-D and 3-D Thermal and Stress Analysis of ARIES-AT Blanket Using ANSYS Conservative SiC/SiC stress limit from Town Meeting: Max. allowable thermal + pressure s = 190 MPa Pressure Stress Analysis of Inner Shell of Blanket Module (Max. s =116 MPa) Thermal Stress Distribution in Toroidal Half of Outboard Blanket Module (Max. s =113 MPa) Pressure Stress Analysis of Outer Shell of Blanket Module (Max. s =85 MPa) ARIES: Fusion Power Core and Power Cycle Engineering/ARR 11

12 Develop Plausible Fabrication Procedure and Minimize Joints in High Irradiation Region Example Procedure for ARIES-AT Blanket 1. Manufacture separate halves of the SiC f /SiC poloidal module by SiC f weaving and SiC Chemical Vapor Infiltration (CVI) or polymer process; 2. Insert the free-floating inner separation wall in each half module; 3. Braze the two half modules together at the midplane; Butt joint Mortise and tenon joint Lap joint Tapered butt joint Double lap joint Tapered lap joint ARIES: Fusion Power Core and Power Cycle Engineering/ARR 12

13 ARIES-AT Blanket Fabrication Procedure Comprises: 1. Manufacturing separate halves of the SiC f /SiC poloidal module by SiC f weaving and SiC Chemical Vapor Infiltration (CVI) or polymer process; 2. Inserting the free-floating inner separation wall in each half module; 3. Brazing the two half modules together at the midplane; 4. Brazing the module end cap; 5. Forming a segment by brazing six modules together (this is a bond which is not in contact with the coolant); and 6. Brazing the annular manifold connections to one end of the segment. ARIES: Fusion Power Core and Power Cycle Engineering/ARR 13

14 Divertor Design Approach Relies on Community Interaction and Innovative Solution to Maximize Performance PFC and Physics Community Interaction Tungsten as plasma-interactive material ALPS liquid divertor option collaboration Fully radiative divertor to maintain reasonable peak heat fluxes, ~ 5 MW/m 2 Provide Guidance for R&D e.g. MHD Effects for Liquid Metal Cooled Divertor Minimize MHD effect by design choice; use of coatings, insulating inserts orsic pipes However, solution must be confirmed by R&D Divertor Coolant Compatible with Blanket Coolant and/or Power Cycle Fluid ARIES-RS: Li in insulated channel (same coolant as blanket) ARIES-ST: He coolant (from power cycle)+high heat flux porous media (Pb-17Li as blanket coolant) ARIES-AT: Pb-17Li in SiC/SiC channel (same coolant as blanket) Assess Key Limiting Issue Detailed Analysis and Innovative Solution to Maximize Performance of Coolant/Material/Concept Combination ARIES: Fusion Power Core and Power Cycle Engineering/ARR 14

15 ARIES-ST Divertor Designed for Thermal Expansion Accommodation Tungsten Armor High-temperature He coolant Advanced high heat flux porous media Several SBIR proposals based on similar configuration Initial high heat flux testing at Sandia indicate high heat flux capability for this material combination (~30 MW/m 2 ) 3-D stress analysis Moderate stresses in high heat flux region High local stress at attachment, can be relieved by flexible joint 2 mm 1 mm ARIES-ST Divertor Tube Cross Section HOT COLD 16 mm 3 mm ARIES: Fusion Power Core and Power Cycle Engineering/ARR 15

16 MHD Effects Influence Both Pressure Drop and Heat Transfer Even in Insulated Channels MHD Accommodation Measure for ARIES-AT Divertor Design Minimize Interaction Parameter (<1) (Strong Inertial Effects) Flow in High Heat Flux Region Parallel to Magnetic Field (Toroidal) Minimize Flow Length and Residence Time Heat Transfer Analysis Based on MHD-Laminarized Flow Pb-17Li Poloidal Flow in ARIES-AT Divertor Header Example schematic illustration of 2-toroidal-pass scheme for divertor cooling Poloidal Direction Plasma q'' A A Cross-Section A-A Toroidal Direction ARIES: Fusion Power Core and Power Cycle Engineering/ARR 16

17 Temperature Distribution in Outer Divertor PFC Channel Assuming MHD-Laminarized Pb-17Li Flow B T PFC d Toroidal distance (m) Radial distance (m) Tungsten 0.02 SiC/SiC Pb-17Li LiPb LiPb Moving Coordinate Analysis Inlet Temperature = 653 C W Thickness = 3 mm SiC/SiC Thickness = 0.5 mm Pb-17Li Channel Thickness = 2 mm SiC/SiC Inner Wall Thick. = 0.5 mm Pb-17Li Velocity = 0.35 m/s Surface Heat Flux = 5 MW/m 2 Max. SiC/SiC Temp. = 1000 C ARIES: Fusion Power Core and Power Cycle Engineering/ARR 17

18 Divertor Design Optimized for Stress Limit Accommodation and Acceptable Coolant Pressure Drop Example ARIES-AT Divertor Analysis For 2.5 mm tungsten, SiC/SiC pressure stress ~ 35 MPa (combined SiC/SiC pressure +thermal stress ~ 190 MPa) DP is minimized to ~0.55 MPa B T PFC LiPb LiPb d Pressure Drop (MPa) Inner Channel Orifice PFC Channel Total Toroidal Dimension of Divertor Channel (m) ARIES: Fusion Power Core and Power Cycle Engineering/ARR 18

19 Close Interaction with International Material and Blanket Design and R&D Communities Combination of Low Activation Structural Material + Liquid Breeder Result in Attractive, High Performance Blankets ARIES-RS: Li + Vanadium; ARIES-ST: Pb-17Li+FS+He; ARIES-AT: Pb-17Li+SiC/SiC Recent Example of Interaction with International Material and Design Communities Organize International Town Meeting to bring together international (US, EU and Japan) material and design SiC/SiC communities (ORNL, Jan 2000) Current material development and characterization status Latest SiC/SiC-based blanket design: TAURO(EU), DREAM(Japan(), ARIES-AT(US) Key SiC/SiC issues affecting blanket performance Detailed info on website ( Town Meeting was very successful; achievements include: Develop list of properties and parameters for design study Clear R&D need for high temperature high performance blanket Need better-quality material with reasonable thermal conductivity-stoichiometry goal Temperature limit: Compability between Pb-17Li and SiC at high temperature Included in US R&D plan and being carried out in Europe Paper deriving from meeting submitted to FE&D ARIES: Fusion Power Core and Power Cycle Engineering/ARR 19